MAAP4.0.7 analysis and justification for PRA level 1 mission success criteria

International Conference on Advances in Nuclear Power Plants, ICAPP 2008

Volumn 2, Issue , 2008, Pages 1064-1075

  Butler, Jennifer S ^a   Kapitz, Darvin ^b   Martin, Robert P ^a   Seifaee, Farrokh ^b   Sundaram, Ramu K ^b  

^a AREVA NP INC   (United States)

^b AREVA NP   (France)

Author keywords

[No Author keywords available]

Indexed keywords

CORE DAMAGE FREQUENCY; EVENT TREES; FAST COMPUTATION; FAULT-TREES; INITIATING EVENTS; INNOVATIVE SYSTEMS; INTEGRAL SYSTEMS; LEVEL 2; LEVEL OF SAFETIES; LEVEL-1; MISSION SUCCESS; PROBABILITY RISK ASSESSMENT; SEVERE ACCIDENT; THERMAL HYDRAULICS CODES; THERMAL-HYDRAULIC ANALYSIS; THERMAL-HYDRAULIC CALCULATIONS; THERMAL-HYDRAULIC RESPONSE;

ACCIDENTS; CORE DISRUPTIVE ACCIDENTS; NUCLEAR ENERGY; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; PRESSURIZED WATER REACTORS; RISK MANAGEMENT; RISK PERCEPTION;

RISK ASSESSMENT;

EID: 70349974748     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (6)

1. "U.S. EPR Final Safety Analysis Report, " Rev. 0, AREVA NP Inc., December 2007.
2. AREVA NP Document ANP-10274P, "U.S. EPR Probabilistic Risk Assessment Methods Report".
3. "Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, " Addenda to ASME RAS-2002, ASME-RA-Sb-2005.
4. Fauske and Associates, Inc., MAAP4-Modular Accident Analysis Program for LWR Power Plants, vol. 2, Part 1: Code Structure and Theory, prepared for Electric Power Research Institute, May 1994.
5. AREVA NP Document EMF-2103 (NP)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors", ADAMS Accession #, ML032691424, April 2003.
6. AREVA NP Document EMF-2328 (NP)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based"., ADAMS Accession # ML003675736, March 2001. AREVA NP Document EMF-2310 (NP), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, " ADAMS Accession #ML032460863, May 2003.